| A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding Bowen Qiu, Jun Wang, Yangbin Deng, Mingjun Wang, Yingwei Wu, Suizheng Qiu Nuclear Engineering and Technology, 2019 | 86* | 2019 |
| The development of module in-vessel degraded severe accident analysis code MIDAC and the relevant research for CPR1000 during the station blackout scenario J Wang, W Tian, Y Zhang, L Chen, L Li, L Zhang, Y Zhou, G Su, S Qiu Progress in Nuclear Energy 76, 44-54, 2014 | 46 | 2014 |
| Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout Z Guo, R Dailey, T Feng, Y Zhou, Z Sun, ML Corradini, J Wang Reliability Engineering & System Safety 213, 107770, 2021 | 40 | 2021 |
| A sub-channel analysis code for advanced lead bismuth fast reactor J Wang, WX Tian, YH Tian, GH Su, SZ Qiu Progress in Nuclear Energy 63, 34-48, 2013 | 40 | 2013 |
| MELCOR simulation of core thermal response during a station blackout initiated severe accident in China pressurized reactor (CPR1000) J Wang, Y Zhang, K Mao, Y Huang, W Tian, G Su, S Qiu Progress in Nuclear Energy 81, 6-15, 2015 | 34 | 2015 |
| Accident tolerant clad material modeling by MELCOR: benchmark for surry short term station black out J Wang, M Mccabe, L Wu, X Dong, X Wang, TC Haskin, ML Corradini Nuclear Engineering and Design 313, 458-469, 2017 | 32 | 2017 |
| Prediction of falling film evaporation on the AP1000 passive containment cooling system using ANSYS FLUENT code X Wang, H Chang, M Corradini, T Cong, J Wang Annals of Nuclear Energy 95, 168-175, 2016 | 31 | 2016 |
| Experimental Investigation on the Characteristics of Melt Jet Breakup in Water: the Importance of Surface Tension and Rayleigh-Plateau Instability Hui Cheng, Jiyun Zhao, Jun Wang International Journal of Heat and Mass Transfer 132, 388-393, 2019 | 27 | 2019 |
| The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC J Wang, W Tian, Y Fan, K Mao, J Lu, G Su, S Qiu Progress in Nuclear Energy 73, 162-171, 2014 | 26 | 2014 |
| Void fraction measurements of steam–water two-phase flow in vertical rod bundle: Comparison among different techniques Miao Gui, Zhaohui Liu, Bo Liao, Teng Wang, Yong Wang, Zhiqiang Sui, Qincheng ... Experimental Thermal and Fluid Science 109, 109881, 2019 | 24 | 2019 |
| Effect of ATF Cr-coated-Zircaloy on BWR In-vessel Accident Progression during a Station Blackout Z Guo, R Dailey, Y Zhou, Z Sun, J Wang, ML Corradini Nuclear Engineering and Design 372, 110979, 2021 | 22 | 2021 |
| Comparison of CORA & MELCOR Core Degradation Simulation and the MELCOR Oxidation Model Jun Wang, Michael L. Corradini, Wen Fu, Troy Haskin, Wenxi Tian, Yapei Zhang ... the 2014 22th International Conference on Nuclear Engineering, July 7 - July …, 2014 | 22* | 2014 |
| Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out T Feng, J Wang, Y Zhou, P Song, M Wang, R Dailey, W Tian, ... Nuclear Engineering and Design 363, 110678, 2020 | 19 | 2020 |
| Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR) YH Tian, GH Su, J Wang, WX Tian, SZ Qiu Progress in Nuclear Energy 68, 177-187, 2013 | 19 | 2013 |
| Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario J Wang, HJ Jo, ML Corradini Nuclear Technology 204 (1), 1-14, 2018 | 17 | 2018 |
| Experimental investigation on heat transfer performance of C-shape tube immerged in a water pool M Gui, Q Bi, J Wang, T Wang Nuclear Engineering and Design 346, 220-229, 2019 | 16 | 2019 |
| 3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM Y Zhou, J Wang, Z Guo, Y He, Y Zhang, S Qiu, GH Su, ML Corradini Progress in Nuclear Energy 138, 103790, 2021 | 15 | 2021 |
| Accident tolerant fuels (FeCrAl Cladding & Coating) performance analysis in Boiling Water Reactor (BWR) by the MELCOR 1.8. 6 UDGC J Wang, R Dailey, Z Guo, Y Zhou, P Humrickhouse, ML Corradini Nuclear Engineering and Design 371, 110974, 2021 | 14 | 2021 |
| Analysis of KROTOS KS-2 and KS-4 steam explosion experiments with TEXAS-VI R Chen, J Wang, GH Su, S Qiu, ML Corradini Nuclear Engineering and Design 309, 104-112, 2016 | 14 | 2016 |
| Comparison of hydrogen generation rate between CORA-13 test and MELCOR simulation: clad solid-phase oxidation models using self-developed code MYCOAC J Wang, ML Corradini, T Haskin, Y Zhang, Q Lu, W Tian, G Su, S Qiu Nuclear Technology 192 (1), 25-34, 2015 | 13 | 2015 |
MICHAEL CORRADINIUniversity of WisconsinVerified email at wisc.edu
